JENDL-5


Nuclide MAT Numerical Data*1 Comments Figures*2) Sig. table
50-Sn-112 5025 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-113 5028 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-114 5031 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-115 5034 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-116 5037 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-117 5040 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-117m1 5041 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-118 5043 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-119 5046 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-119m1 5047 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-120 5049 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-121 5052 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-121m1 5053 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-122 5055 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-123 5058 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-124 5061 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-125 5064 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table
50-Sn-126 5067 original, 0K, 300K u20 comment Fig1 Fig2 Fig3 table


*1) u20: Data up to 20 MeV.
*2) Fig1, Fig2 and Fig3 are made from pointwise files at 300 K.

Fig1 : Total, elastic and inelastic scattering, capture and fission cross sections
Fig2 : Same as Fig1 but the cross sections are averaged in 70 energy group intervals
Fig3 : Threshold reaction cross sections